A NEUTRONIC STUDY OF THE CULHAM CONCEPTUAL TOKAMAK REACTOR MK II

Abstract

The proposal to use a toroidal fusion reactor vessel with an elliptical minor cross section raises considerable difficulties in the neutronics modelling of the plasma/blanket/shield system. The paper outlines a route to approximating such systems using Monte Carlo techniques; the variation in neutron flux and spectrum, tritium breeding and neutron damage and gas production rates around the minor periphery are given. For the Culham Conceptual Tokamak Reactor Mk II, the variation in these (max/min ~ 1.25) is considerably less than might have been expected with an elliptical cross section of eccentricity 1.75.